ML20239A336
| ML20239A336 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/04/1998 |
| From: | Hoyle J NRC OFFICE OF THE SECRETARY (SECY) |
| To: | Cotter B Atomic Safety and Licensing Board Panel |
| References | |
| CON-#398-19494 LA-2, NUDOCS 9809090048 | |
| Download: ML20239A336 (5) | |
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September 4, 1998
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MEMORANDUM TO:
B. Paul Cotter, Jr.
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Chief Administrative Judge and Licensing Board Panel
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FROM:
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Secretary j
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SUBJECT:
HEARING REQUEST OF THE SEACOAST ANTI-POLLUTION LEAGUE AND THE NEW ENGl.AND COALITION ON NUCLEAR POLLUTION j
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I Attached is a request for hearing dated August 18,1998, and submitted by Robert A. Backus on behalf of the Seacoast Anti-Pollution League and the New England Coalition on Nuclear Pollution.
The petition was filed in response to a notice of a proposed determination by the staff that the issuance of a license amendment to the North Atlantic Energy Service Corporation for Seabrook j
Station Unit No.1 (Docket No. 50-443) would involve no significant hazards considerations. The amendment would revise Technical Specifications on the frequency of surveillance requirements to accommodate fuel cycles of up to 24 months for surveillance that are currently performed at 18-month or other specified outage interval. The notice was published in theFederal Reaister at 63 Fed. Reg. 43200, 43205 (May 6,1998) (copy attached).
The hearing request is being referred to you for appropriate action in accordance with 10 C.F.R.
Sec. 2.772(j).
Attachments: as stated cc:
Commission Legal Assistants OGC i
NRR Lillian M.Cuoco, Esquire Northeast Nuclear Energy Company Robert A. Backus, Esquire l
9909090048 990904 PDR ADOCM 05000443 0
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4 BACKUs. MEYER. $CLOMON. USNP' Rooo & BRANCH Atto RN CYS A? (,AW ne Lowcu. srRec W AUS 21 P1 :4] ACMITTE:
I ALS RO.Boxs 4 STEVEN A. SOLOMON
.TO HA,,AcH L SCT,S,AR JENNIFER ROOD **
MANCHESTER. NH Oslos.pyps "To MAINE SAR S.J. BRANCH L4 or couwst.
'603)668-72'*2 CARIN HOOD-TUCKER ads -
aosEar A. sac <us FAX '6038 668-0730 NANCYE. HART August 18,1998 Judge Paul Cotter, Jr., Chairman 4
i Atomic Safety and Licensing Board Panel Nuclear regulatory Commission Washington, DC 205L5-0001 Dr. Charles W. Kelber i
Atomic Safety and Licensing Board Panel Nuclear Regulatory Commission Washington, DC 20555-0001 Dr. Linda Little 5000 Hermitage Drive Raleigh, NC 27612 RE:
North Atlantic Energy Service Corporation Seabrook Station, Unit No.1 Docket No. 50-443 j
ASLBP No. 98-746-05-LA
Dear Administrative Judges:
I am enclosing the SAPIJNECNP Reply to Staff Answer to Contentions and the SAPUNECNP Reply to NAESCO Response to Proposed Contentions as provided by 10 CFR
- 2.706.
i I also wish to advise the Board that I have just learned that, in the Federal Register for August 12,1998, there is another amendment request "to accommodate fuel cycles of up to 24 months for surveillance that are currently performed at each 18 month or other specified outage intervals." This is apparently the third in the anticipated " series of requests" referred to by Mr.
Feigenbaum in his April 8,1998 letter transmitting License Amendment Request 98-03.
n%r 24oa54 2,y.
- The surveillance proposed to be changed "to accommodate" the 24-month cycles are:
digital rod positian indication; transfer of IE Bus Power from Normal to Alternato Source:
Emergency Diesel Generator Surveillance; Onsite Power Distribution - Trip Circuit for Invener, 125 Volt D.C. Batteries and Charges; Containment Penetration Conductor Overcurrent Protective
' Devices and Protective Devices for Class IE Power Sources Connected to Non-Class IE Circuits; Motor Operated Valves Thermal Overload Protection.
The notice adds: "In addition, the components listed in Technical Specification 4.8.2.2, D.C. Sources - Shutdown - 125 V DC Batteries and Charges, have been evaluated to support an extension in frequency to 24 months." Federal Register, Vol. 93, No.155, pages 43,205 46, August 12,1998.
Petitior?rs bring this to the Board's attention in light of the argument over whether this proceeding invc,ves a planned operational change to a 24 n.onth fuel cycle, with the change being applied for in segments, or whether it involves only a decrease in steam generator inspections.
The most recent amendment request cenainly appears relevant to this question.
Should the Board rule that this proceeding must be limited to only steam generator inspections, Puit;oners would chen respectfully request that this letter be considered a new request for a he sing as to the changes specified in the amendment request in the August 12 Federal Register.
Very truly yours,
>f ju r jRobdn A. Backa; RAB/str Enc.
cc:
SAPL NECNP David Lochbaum 6
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43200 Federal Register /Vol. 63, No.155 / Wednesday, August 12,1998 / Notices Week of August 24--Tentative NUCLEAR REGULATORY liowever, should circumstances change p.
COMMISSION during the notice period such that d
Tuesday, August 25 failure to act in a timely way would g
Biweekly Notic% Applications and result, for example, in derating or ai 10:00 a.m.-Briefing on 10 CFR Part Amendments to Facility Operating shutdown of the facility, the 70--Proposed Rulemaking, Licenses involving No Significant Commission may issue the, license p
" Revised Requirements for the Hazards Considerations amendment before the expiration of the fc Domestic Licensing of Special 30-day notic,e period, provided that its tl Nuclear Material" (Public Meeting)
- 1. Ilackgmund final determmation is that, the h
(Contact: Elizabeth Ten Eyck,301-Pursuant to Public Law 97-415, the amendment involves no significant ri 415-7212)
U.S. Nuclear Regulatory Commission hazards consideration. The final s
Wednesday, August 26 (the Commission or NRC staff)is determination will consider all public y
publishing this regular biweekly notice. and State comments received before v
2:00 p.m.-Briefing on Status of Public Law 97-415 revised section 189 action is taken. Should the Commission f.
Activities with CNWRA and HLW of the Atomic Energy Act of 1954, as take this action, it will publish in the Program (Public Meeting)(Contact: amended (the Act), to require the Federal Register a notice of issuance n
Mike Bell,301--415-7286)'
Commission to publish notice of any and provide for opportunity for a r
3:30 p.m.-Affirmation Session (Public amendments issued, or proposed to be hearing after issuance. The Commission Meeting)(if needed) issued, under a new provision of section expects that the need to take this action t
189 of the As. This provision grants the will occur very infrequently.
e Week of August 31 Commission the authority to issue and Written comments may be submitted Wednesday, September 2 make immediately effective any by mail to the Chief, Rules and amendment to an operating license Directives Branch, Division of i
10:00 a.m.-Briefing on PRA upon a determination by the Administration Services, Office of Implementation Plan (Public Commission that such amendment Administration, U.S. Nuclear Regulatory i
Meeting) (Contact: Tom King,301-involves no significant hazards Commission Washington, DC 20555-415-5828) consideration, notwithstanding the 0001, and should cite the publication i
11:30 a.m.-Affirmation Session (Public Pendency befora the Commission of a date, and page number of this Federal Meeting)(if needed)
M9. uest for a heanng from any person.
Register notice. Written comments may This biweekly notice includes all also be delivered to Room 6D22. Two Thursday September 3 notices of amendments issued, or White Flint North,11545 Rockville proposed to be issued from July 20, Pike, Rockville, Marylaad from 7:30 10:00 a.m. and 1:30 p.m-All 1998, through July 31,1998. The last a.m. to 4:15 p.m. Federal workdays.
Employees Meetings (Public biweekly notice was published on July Copies of written comments received Meetings) on "The Green" Plaza 29,1998 (63 FR 40551).
may be examined at the NRC Public Area between buildings at White Document Room, the Gelman Building, Flint (Contact: Bill Hill-301-115-Notice of Considerate.n ofIssuance of 2120 L Street, NW., Washington, DC.
1661)
Amendments to Facility Operating The filing of requests for a hearing and Licenses, Proposed No Significant Petitions for leave to intervene is The schedule for Commission llazards Consideration Determination, discussed below.
meetings is subject to change on short and Opponunity for ailcaring By September 11,1998, the licensee notice. To verify the status of meetings The Commission has made a may file a request for a hearing with call (recording)--(301) 415-1292.
{r Posed determination that the respect to issuance of the amendment to Contact Person for more information:
11 wing amendment requests involve the subject facility operating license and Bill Hill (301) 415-1661.
no significant hazards consideration.
any person whose interest may be The NRC Commission Meetin8 Under the Commission's regulations in aff'ected by this proceeding and who Schedule can be found on the Internet to CFR 50.92, this means that operation wishes to participate as a party in the at: http://www.nrc. gov /SECY/smj/
of the facility in accordance with the proceeding must file a written request schedule.htm proposed amendment would not (1) for a hearing and a petition for leave to This notice is distributed by mail to involve a significant increase in the intervene. Requests for a hearing and a several hundred subscribers;if you no probability or consequences of an petition for leave to intervene shall be longer wish to receive it, or would like accident previously evaluated; or (2) filed in accordance with the to be added to it, please contact the create the possibility of a new or Commission's " Rules of Practice for Office of the Secretary, Attn: Operations different kind of accident from any Domestic Licensing Proceedings"in to Branch, Washington, D.C. 20555 (301-accident previously evaluated; or (3)
CFR Part 2. Interested persons should 415-1661). In addition, distribution of involve a significant reduction in a consult a current copy of 10 CFR 2.714 this meeting notice cyer the Internet margin of safety. The basis for this which is available at the Commission's system is avail ole. If you are interested proposed determination for each Public Document Room, the Gelman in receiving this Commission meeting amendment request is shown below.
Building,2120 L Street, NW.,
schedule electronically, please send an The Commission is seeking public Washington, DC and at the local public elect onic message to wmh@nrc. gov or comments on this proposed document room for the particular dkw@nrc. gov.
determination. Any comments received facility involved. If a request for a within 30 days after the date of hearing or petition for leave to intervene Dated: August 7,1998.
publication of this notice will be is filed by the above date, the william M. llill, lr.,
considered in n Aing ar* T.nal Commission or an Atomic Safety and SECY Tmcking Officer. Office of the deterrrr. nation.
Licensing Board, designated by the SecrermY Normally, the Commission will not Commission or by the Chairman of the
[FR Doc. 98-21667 Filed 8-7-98; 4:14 pml jssue the amendment until the Atomic Safety and Licensing Board sums coos neo-oi-m expiration of the 30-day notice per od.
Panel, will rule on the request and/or
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Federal Register /Vol 63, No.155/Wr esday, August 12,1998 / Notices 43201 i
petition; and the Secretary or the Those permitted to intervene become Description of amendment request:
designated Atomic Safety and Licensing parties to the proceeding, subject to any Baltimore Gas and Electric Company Board willissue a notice of a hearing or hmitations in the order granting leave to (BGE) request a modification involvin en appropriate order.
Intervene, and have the opportunity to replacing the service water (SRW) heat As required by 10 CFR 2.714, a participate fully in the conduct of the exchangers with new plate and frame petition for leave to intervene shall set hearing, including the opportunity to heat exchangers having increased l
forth with particularity the interest of present evidence and cross-examine thermal performance capability, A I
the petitioner in the proceeding, and witnesses.
how that interest may be affected by the If a hearing is requested, the similar license amendment dated results of the proceeding. The petition Commission will make a final February 8,1998, was granted to should specifically explain the reasons determination on the issue of no Operating License No. DPR-53-Calvert why intervention should be permitted significant hazards c.tideration. The Cliffs Nuclear Power Plant, Unit 1.
with particular reference to the final determination will serve to decide The planned modification for Unit 2 following factors:(1) the nature of the when the hearing is held-is virtually identical to the one just petitioner's right under the Act to be If the final deterrrdnation is that the completed for Unit 1 during the spring made a party to the proceed;ng: (2) the amendment request involves no 1998 refueling outa e. The only n:ture and extent of the petitioner's significant hazards consideration, the exception is the adfition of an extra property, financial, or other interest in Commission may issue the amendment manual valve in the Unit 2 system to the proceeding: and (3) the possible and make it immediately effective, isolate the bypass line for maintenance.
effect of any order which may be notwithstanding the request for a This additional manual valve is needed entered in the proceeding on the hearing. Any nearing held would take due to the change in location of the tie-petitioner's interest. The petition should place after issuance of the amendment.
in to the main header. (The Unit 1 also identify the specific aspect (s) c.'the If the final determination is that the bypass line ties into the main header subject matter of the proceeding as to amendment request involves a downstream of a control valve; which petitioner wishes to intervene.
significant hazards consideration, any therefore,it did not need a separate Any person who has filed a petition for hearing held would take place before isolation valve for maintenance.)
Inve to intervene or who has been the issuance of any amendment' The saltwater and SRW piping admitted as a party may amend the A request for a heating or a petition confi uration will be modified as
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petition without requesting leave of the for leave to intervene must be filed with necessary to allow proper fit-up to the 8
Board up to 15 days prior to the first the Secretary of the Commission, U.S.
newc Ponents. A flow control prehearing conference scheduled in the Nuclear Regulatory Commission, scheme to throttle saltwater flow to the proceeding. but such an amended Washington, DC 20555-0001, Attention: heat exchangers and the associated petition must satisfy the specificity Rulemakings and Adjudications Staff, or bypass lines will be added. Saltwater requirements described above.
may be delivered to the Commission's strainers with an automatic flushing Not liter than 15 days prior to the first Public Document Room, the Gelman arrangement will be added upstream of prehuring conference scheduled in the Building,2120 L Street, NW.,
each heat exchanger. The maiority of the proceeding, a petitioner shall file a
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supplement to the petition to intervene Washington DC, by the above date. A h,
P ysical work associateo with this which must include a list of the copy of the petition should also be sent modi'ication is restricted to the SRW contentions which are sought to be to the Office of the General Counsel, Pump room.
litigated in the matter. Each contention U.S. Nuclear Regulatory Commission.
Basisforproposed no significant Washington, DC 20555-0001, and to the hazards consideration determination:
must consist of a specific statement of attorney for the licensee.
As required by 10 CFR 50.91(a), the the issue oflaw or fact to be raised or Nontlmely filings of petitions for licensee has provided its analysis of the controverted. In addition, the petitioner shall provide a brief explanation of the leave to intervene, amended petitions, issue of no significant hazards supplemental petitions and/or requests consideration, which is presented bases of the contention and a concise for a hearing will not be entertained below:
statement of the alleged facts or expert absent a determination by the opinion which support the contention Commission, the presiding officer or the in the probability or consequences of an
- 1. Would not involve a significant increase and on which the petitioner intends to Atomic Safety and Licensing Board that accident previously evaluated.
rely in proving the contention at the heiring. The petitioner must also the petition and/or request should be None of the systems associated with the provide references to those specific granted based upon a balancing of Proposed modification are accident initiators.
factors specified in to CFR The SW and SRW Systems are used to sources and documents of which the petitioner is aware and on which the 2.714!a)(1)(i)-(v) and 2.714(d) mitigate the effects of accidents analyzed in 1
petitioner intends to rely to establish For further details with respect to this
'h
^
d those facts or expert opinion. Petitioner actic,n, see the application for Rep T s ands st r
e ame:ndment which is available for cooling to safety-related equipment following roust provide sufficient information to public inspection at the Commission's an accident. They support accident I
show that a genuine dispute exists with Pchlic Document Room, the Gelman mitigation functions; therefore, the proposed
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the applicant on a materialissue oflaw modification does not increase the or fact. Contentions shall be limited to Building,2120 L Street, NW.,
probability of an accident previously l
mitters within the scope of the Washington, DC, and at the local public evaluated.
document room for the particular The proposed modification will increase amendment under consideration. The facility involved.
the heat rem val capacity of the SRW cont:ntion must be one which, if S S'** Th' d*"',gn provided under this Y
proven, would entitle the petitioner to Baltimore Gas and Electric Company, activity ensures that the safety features relief. A petitioner who fails to file such Doclet No. 50-318, Calvert Cliffs provided by the SW and SRW are a supplement which satisfies these ucle r Plant, Unit No. 2, Calvert m
ain d a in s
se ced.
requirements with respect to at least one
- f' f};
contrntion will not be permitted to Date of omendment request: July 20, radiological consequences of an accident equipment required to mitigate the particip:te as a party 1998.
described in the UFSAR is enhanced by the
,.q Fed:rcl Regist:r/Vol. 63, No. ISS/ Wednesday, August 12,1998 / Notices 43205 l
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Mcal Public Document Roorn involved with this change. There are no or other specified outage interval.
location: Law / Government Publications changes to the source term, containment Specifically, the following TS isolation or radiological release assumptions surveillance requirements would be Section, State Library of Pennsylvania,
[ REGIONAL DEPOSITORY) Walnut
',[,a revised by the proposed change: 4.1.3.3, l
"5 ra o cl tation Digital Rod Position Indication:
Street and Commonwealth Avenue, Box lupdated final safety analysis reportl UFSAR.
4.8.1.1.1.b. A.C. Sources-Operating-
)
1601, Harrisburg, PA 17105.
The new setpoint will continue to initiate the Transfer of 1E Bus Power from Normal l
Attorneyfor hcensee: Ernest L. Blake, automatic ECCS transfer from the injection i
Jr., Esquire, Shaw, Pitman, Potts &
mode to the recirculation mode and provide to Alternate Source: 4.8.1.1.2.f.1 through l
Trowbridge,2300 N Street, NW.,
the alarm to alen the operator (s) to begin the 15, A.C. Sources-Operating-I Washington, DC 20037, manual actions necessary to complete the Emergency Diesel Generator NRC Project Dimetor: Cecil D.
transfer to the recirculation mode. Manual Surveillance: 4.8.3.3, Onsite Power operator action is required to complete the Distribution-TriPCircuit For Inverter Thomas.
switchover to the recirculatmn mode. With I-2A; 4.8.2.1.c. d a f, D.C. Sources-North AtlanticEnergyService the new setpoint, sufficient time remains Operating-125V D.C. Batteries and Corporation, Docket No. 50-443, available for the operator (s) to complete the Seabmok Station, Unit No.1, transfer prior to receipt of the RWST EMITY Chargers; 4.8.4.2.a.1) & a.2),
alarm and reaching the vortexing level in the Containment Penetration Conductor Rockingham County, New Hampshire RWST. Therefore, the proposed change does Overcurrent Protective Devices and Date of amendment request:May 20, not create the possibility of a new or different Protective Devices for Class 1E Power 1998.
Lind of accident from any previously Sources Connected to Non-Class 1E Description of amendment wguest:
analyzed.
Circuits; 4.8.4.3, Motor O rated Valves Thi proposed change would revise the
- 3. The proposed change does not involve Therma 1 Over1ond Protection. In Refulling Water Storage Tank (RWST) a significant reduction in a margin of safety.
addition, the components listed in The design bases for the RWST Level Low.
setpoint associated with Automatic L w setPoint is to ensum that the minimum Technical Specification 4.8.2.2, D.C.
Switchover to the Containment Sump.
volume of water to support the assumptions Sources-Shutdown-125V DC This change would require a revision to made in the safety analysis is injected prior Batteries and Chargers, have been th3 Engineered Safety Features to switchover and that there is adequate time evaluated to support an extension in Actuation System Instrumentation Trip available for the operators to complete the uenc to 24 months (+25%).
Setpoints, Table 3.3-4, Functional Unit manual actions necessary to complete the frehasis[rp sed no significant 8.b, RWST Level-Low Low, along with switchover to the recirculation mode prior t hazards cons ration determination:
actuation of the RWST EMPTY alarm. The As N9uired by 10 CFR 50.91(a), the cssociated Bues Section 3/4.3.2.
minimum infection volume assumed in the licensee has provided its analysis of the Ba:isforpro osed no significant hesords consi[eration determination:
accident analyses, and time required for the issue of no significant hazards Perator(s) to initiate and complete manual acu m t c mP ete switchover to the consideration, which is presented As required by to CFR 50.91(a), the l
lic:nsee has Provided its anal sis of the recirculation mode pnor to receipt of the below:
Y issu3 of no significant hazards RWST EMPTY alarm, remains unaffected by
- 1. The proposed changes do not involve a consid: ration, which is presented this chang'e. Therefore, the proposed change significant increase in the probability or below:
does not involve a significant reduction in a ccmsequences of an accident previously margin g,,f,ty.
evaluated.
- 1. The proposed change does not involve a significant increase in the probability or The NRC staff has reviewed the The proposed changes do not adversely consequences of an accident previously licensee's analysis, and based on this affect accident initiators or precursors nor evrlutted-review, it appears that the three alter the design assumptions, conditions, Thi proposed change does not adversely standards of 50.92(c) are satisfied.
c nfiguration of the facility or the manner in which the plant is operated. The pro sed effect r:cident initiators or precursors and Therefore, the NRC staff proPosos to changes do not alter or prevent the a ility of does not alter the design assumptions determine that the amendment request structures, systems, or components (SSCs) to r
(ffecting the ability of the RWST and the involves no significant hazards perform their intended function to mitigate i
ECCS (Emergency Core Cooling System) r consideration, the consequences of an initiating event pumps to mitigate the consequences of an Local Public Document Room within the acceptance limits assumed in the 1
(ccidrat.
Revising the RWST Level tow-Iow location: Exeter Public Library, Updated Final Safety Analysis Report setpoint has a negligible effect on the Founders Park, Exeter, NH 03833.
(UFSAR). The proposed changes are administrative in nature and do not change I
oper-ting margin for the RWST. The revised Attorneyfor licensee:Lillian M.
the level of programmatic controls or the setpoint assures that the minimum RWST Cuoco, Esq., Senior Nuclear Counsel, pr cedural details associated with volume assumed in the accider.t analyses is Northeast Utilities Service Company, aforementioned surveillance requirements.
inject;d prior to switchover to the P.O. Box 270, Hartford, CT 06141-0270.
Changing the frequencies of the recirculation mode. The effect on NIIC Pro 1ect Dimeror: Cecil aforementioned surveillance requirements
~
containment flood level, equipment qualification, and pH of the containment
%omas.
from at least once per 18 months to at least once per refueling interval does not change sump cnd the containment spray (Nd North Atlantic Energy Service the basis for the frequencies. The frequencies remain within the limits assumed.a th'e Corporation, Dociet No. 50--443, were chosen because of the need to perform tccid nt analyses.
Seabrook Storion, Unit No. L these verifications under the conditions that Th:refore, the proposed change does not Rockingham County, New 1fornpshs.
are normally found during a plant refueling j
m involve a significant increase in the probability or consequences of an accident Date of amendment request: May 21, outage, and to avoid the potential of an unplanned transient if these surveillance previously evaluated.
1998 were conducted with the plant at power.
- 2. The proposed change does not create tlie Description of amendment 7 quest:
peraung c p' P*'I"""***
- '"*'"I E "'P**"
9 possibility of a new or different kind of The proposed change woul3 6 vise s was naluated ydetennine eccidrnt from any previously analyzed.
selected Technical SP"cification (TS) the impact of extending the surveillance Tha setpoint change does not affect the surveillance requirements to intervals. This evaluation included a review function of the level monitoring channels or accommodate fuel cycles of up to 24 of surveillance results, preventative any function of the accident mitigation months for surveillance that are maintenance records, and the frequency and equipment associated with the RW3T. No currently performed at each 18 month type of corrective maintenance activities, a new components or physical changes are i
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43206 Federal Register /Vol. 63, No.155/ Wednesday, August 12,1998 / Notices failure mode analysis, and consultation with being made to the Technical Specification types ofinternal protective coatings and the respective system engineer. The required safety limits or safety system liners used in the piping and evaluations conclude that the subject SSCs settings that would adversely affect plant components of the systems.The are highly reliable, that presently do not safety. The proposed changes are proposed change also indicates that exhibit time dependent failure modes of administrative in nature and do not change Periodic maintenance, surveillance, significance, and that there is no indication the level of programmatic controls and and inspections would be conducted to that the proposed extension could cause procedural details associated with the deterioration in the condition or performance aforementioned surveillance requirements.
ensure that coating or liner degradation of the subject SSCs. There are no known From the evaluations performed on the would be promptly detected and mechanisms that would significantly degrade subject SSCs there are no indications that corrected to provide reasonable the performance of the evaluated equipment potential problems would be cycle-length assurance that the systems can perform during normal plant operation. Although dependent or that potential degradation their safety related functions.
there have been generic or repetitive failures would be significant for the time frame of Basis forproposed no significant of some components in the past, which may interest and, therefore, increasing the hazards consideration determination:
have affected the ability of the SSCs to surveillance interval to the boundmg limit of lus 25%) will have As required by 10 CFR 50.91(a), the consistently and successfully perform their 30 months (24 months fect on safety, licensee has provided its analysis of the safety function, those items have been little, if any, adverse af resolved through design changes and rewnrk The proposed changes to the surveillance issue of no significant hazards such that they have not recurred. There have intervals are still consistent with the basis for consideration, which is presented b3en no repetitive failures or time dependent the intervals and the intent and method of below:
failures that were significant in nature which performing the surveillance is unchanged.
The proposed change does not would have prevented the SSCs from,
Deletion of the restriction "during involve significant hazards performing their intended safety function.
shutdown" where this restriction is stated consideration because the changes Deletion of the restriction during effect on will permit performance of certain w uld not:
safe operation of the plant is given prior to maintenance and testing act.vities during conduct of a particular surveillance in a conditions or modes other than shutdown.
- 1. Involve a significant increase in the condition or mode other than shutdown.
North Atlantic will ensure, through the probability or consequences of an accident Since the proposed changes only affect the implementation of appropriate previously evaluated.
surveillance intervals for SSCs that are used administrative controls, that proper regard to The SWS (Service Water System? provides to mitigate accidents (sic), the changes do not their effect on safe operation of the plant is cooling water directly or indirectly to a affect tne probability or consequence of a given prior to conduct of a particular multitude of mitigating and support systems previously analyzed accident. While the surveillance in a condition or mode other such as safety injection, containment spray, proposed changes will lengthen the intervals than shutdown. In addition, use of the and RBCCW iReactor Building Closed.
between surveillance. the increase in subject SSCs during normal plant operation, Cooling Water). Therefore either directly or intarvals has been evaluated. Based on the combined with their previous history of indirectly, the SWS is credited in the reviews of the surveillance tests, inspections, availability and reliability, provide assurance mitigation of virtually all analyzed operating and maintenance activities, it is concluded that the proposed changes will not affect the events and accidents. However, there are no that there is no significant adverse impact on reliability of the subject SSCs. Thus, it is failures of the SWS which would directly the reliability or availability of these SSCs-concludef that the subject SSCs would be initiate any of the licensing basis accidents.
Since there are no changes to previous available upon demand to mitigate the Therefore, the probability of occurrence of accident analyses, the radiological consequences of an accident and, therefore, accidents reviously evaluated is not consequences associated with these analyses there is no impact on the margin of safety.
increased y this activity.
remain unchanged, therefore, the proposed changes do not involve a signif cant increase The NRC staff has reviewed the The SWS is comprised of two separate and in the probability or consequences of an licensee's analysis, and based on this independent trains, each capable of accident previously evaluated.
review, it appears that the three pr viding the c ling capacity required for "T
- 2. The pro ed changes do not create the standards of 50.9Mc) are satisfied.
[ ngle h t chan o in possibilit o a new or different kind of Therefore, the NRC staff proposes to will not influence the consequences of an he proposed cha ges70 not alter the petedne ty d,ie amendment request accident. Only a common mode loss of SWS involves no significant hazards function could affect accident consequences.
design assumptions, conditions, consideration.
it can be postulated that lining material could configuration of the facility or the manner in Local Public Document Room be released as a result of the SWS response which the plant is operated. There are no changes to the source term, containment location: Exeter Public Library, to an accident or as a result of a seismic isolation or radiological release assumptions Founders Park, Exeter, NH 03833.
event, resulting in heat exchanger blockage in used in evaluating the radiological Attorneyforlicensee: Lillian M.
both trains (common mode). However, the consequences in the Seabrook Station Cuoco, Esq., Senior Nuclear Counsel, discussi n below provides the basis for UFSAR. Existing system and component Northeast Utilities Service Company, F ncluding that lining degradation will not
'""9 " " * "
- redundancy is not being changed by the P.O. Box 270, Hartford, CT 06141-0270' In mPom to a Safety Wecth Actuauon proposed changes. The proposed changes NRC Project Director: Cecil O-Signal or a Loss of Normal Power event, the hzve no adverse impact on component or
- Thomas, quantity of flow in safety related SWS heat system interactions. The proposed changes are administrative in nature and do not Northeast Nuclear Energy Company, et exchangers may increase significantly, imparting higher loads on the pipe linings change the level of programmatic. controls al., Docket No. 50-336, Millstone O *" *" 'YP **"Y P""
- d"#""*
and procedural details associated with the Nuclear Power Station. Unit No. 2. New operation. In spite of this flow incretse. it is aforementioned surveillance requirements.
Therefore, since there are no changes to the London County, Connecticut considered to be much more likely that any design assumptions, conditions, Date of amendment request: July 2, lining degradation will occur and be detected under normal operating conditinnt, and will configuration of the tacility, or the manner in 1998.
which the plant is operated and surveilled.
Descript on of amendment request; be corrected prior to the occurrence of an the proposed changes do not create the Re proposed amendment would revise event of the type discussed above. SWS pump now surmilances, perf rmed possibility of a new or different kind of the uP ated Final Safety Anal) sis periodiudly during normal operation. subject d
accident from any previously analyzed.
- 3. The proposed changes do not involve a Report U,SAR) by changing FSAR significant portions of the SWS to flow levels significant reduction in a margin of safety.
Sections 9.7.2, " Service Water," and 9.4, which equal or exceed those expected to There is no adverse impact on equipment
" Reactor Building Closed Cooling occur during accidents. Any degraded lining design or operation and there are no thanges Water,"to discuss the use of various material prone to be released during an l